ML20095G550
| ML20095G550 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/24/1984 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20095G555 | List: |
| References | |
| NUDOCS 8408280104 | |
| Download: ML20095G550 (2) | |
Text
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s SOUTH CAROLINA ELECTRIC Pc GAS COMPANY POST OFFICE 764 cowueia, sours canous 292i8 o w. o,.O. x August 24, 1984
~2'a','.%S Mr. Harold R. Denton, Director i
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 i
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 a
Operating License No. NPF-12 Technical Specification Change to Table 2.2-1
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Dear Mr. Denton The Virgil C.
Summer Nuclear Station is designed for full load rejection (runback to house load) without a turbine trip or reactor trip.
Data taken during partial load rejection tests conducted during our Phase III startup test program revealed that the plant did not have the capability to handle a full load a
rejection without tripping using the protection and control g
system setpoints specified by Technical Specifications and Westinghouse.
Following an indepth analysis of this problem by Westinghouse, 1
they have recommended changes to the overtemperature delta-T and a
steam generator low level trip setpoints and to the steam dump control system setpoints.
These setpoint changes are a result of control and protection system evaluations.
The safety analysis design basis will continue to be met.
r South Carolina Electric and Gas Company (SCE&G) requests that Tables 2.2-1 and 3.3-4 of Technical Specifications be revised as
[
shown on the attached sheets.
The revisions to Table 2.2-1 which were requested in correspondence to you dated July 22, 1983 were assumed in the analysis.
SCE&G has determined that a finding of no significant hazards is appropriate, because these setpoint changes remain bounded by the existing safety analyses for the Virgil C.
Summer Nuclear Station.
m This amendment has been reviewed and approved by both the Plant Safety Review Committee and the Nuclear Safety Review Committee.
The stataments and matters set forth herein are true and correct to the best of my knowledge, information and belief.
As required
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by Title 10 of the Code of Federal Regulations, Part 170 (10CFR170), a check in the amount of one hundred fifty dollars 8408280104 840824 PDR ADOCK 05000395 l l y'.lhe#f/.Sc.co
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~Mr Harold R. Denton,
- Technical' Specification Ch'ange j
Table 2.2-1 l '. '.
Augnst: 24, 1984 1s Page'#2 s
($150.00).is enclosed to~ initiate the processing of this request.
If =you have any questians, please advise.
-Very truly yours,
'\\
A O. W. Dixon, Jr.
SMC/.OWD/gj cc:
V. C.
Summer C. A. Price T. ' C. Nichols, Jr./O. W. Dixon, Jr. -
C. L. Ligon (NSRC)
E.-H.
Crews, Jr.
K.
E. Nodland W.' A.. Williams, Jr.
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R. A. - Stough E. C. Roberts G. Percival D
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Nauman-C. W. Hehl 1
' J. - P... O ' Re i lly.
J. B.
Knotts, Jr.
Group Managers-H. G. Shealy NPCF O.
S.' Bradham '
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